Investigation of tritium breeding ratio using different coolant material in a fusion-fission hybrid reactor


Sahin H. M. , Tunç G., Şahin N.

INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, vol.41, no.17, pp.7069-7075, 2016 (Journal Indexed in SCI) identifier identifier

  • Publication Type: Article / Article
  • Volume: 41 Issue: 17
  • Publication Date: 2016
  • Doi Number: 10.1016/j.ijhydene.2015.11.174
  • Title of Journal : INTERNATIONAL JOURNAL OF HYDROGEN ENERGY
  • Page Numbers: pp.7069-7075

Abstract

The aim of this study is to investigate tritium breeding ratio (TBR) and first wall material damage parameters such as displacement per atom (DPA), gas production of various coolants with Li2C2 tritium breeding material using the three different data libraries (ENDF/B.V, ENDF/B.VI and CLAW IV). Hence, FLiNaK, enriched (90% Li-6) natural lithium, lithium lead eutectic alloy (Li17Pb83) and FLiBe (Li2BeF4) were used as a coolant (moderator) material for the calculation of the tritium breeding ratio and gas production parameters in a hybrid reactor. Neutronic calculations were performed by Monte Carlo Neutron-Particle Transport code MCNPS version 1.40 under a neutron wall loud of 2.25 MW/m(2) (10(14) n/s) by full reactor power for one year. All examined coolant materials were achieved minimum required tritium breeding ratio (TBR > 1.05) and based on radiation damage limits. When the enriched (90%) lithium coolant with lithium carbide breeder used in fusion fission (hybrid) reactor, vanadium alloy first wall will be replaced every 3.6 and 6.7 years for DPA and Helium production, respectively. Copyright (C) 2015, Hydrogen Energy Publications, LLC. Published by Elsevier Ltd. All rights reserved.